Experimental analysis of radioactivity released by low-level and intermediate-level radioactive waste

Abstract

The purpose of this research project was to determine, under simulated repository conditions, the release of airborne radionuclides from cemented ion exchange resins originating from reactor coolant purification systems of a pressurised water reactor. The radionuclides considered were H3, C14, I129, Fe55, Ni63 and alpha-emitters. As radionuclides H3, C14, and I129 can form volatile compounds, they are of special concern with regard to disposal. Fe55 and Ni63, which occur in ion exchange resins in reactor purification systems, are relatively long-lived and difficult to determine by radiochemical analysis techniques. The project also includes analysis of the release of the above radionuclides via the water pathway and the further development of analysis techniques.